Abstract: An apparatus for dismantling a radioactively contaminated tubular installation part which is located under water contains a base part which can be fixed to the installation part and in which a rolling cutting apparatus is mounted. The rolling cutting apparatus can be positioned in or on the installation part and has at least one cutting roller which can be moved to the inner or outer surface of the installation part and can be moved along it. The apparatus can be used to dismantle and remove even installation parts to which access is difficult, for example the cyclones which are installed in the water/steam separator of a boiling water reactor.
Type:
Grant
Filed:
December 9, 2005
Date of Patent:
October 28, 2008
Assignee:
Areva NP GmbH
Inventors:
Reinhardt Strobel, Bruno Dippel, Josef Forster
Abstract: This invention relates to a circuit breaker (1) for high or medium voltages, of the type having a drive bar (70) coupled to a drive member, and a circuit-breaking chamber (2) facing it and having two contacts (3, 4), each contact (3, 4) including a main contact (30, 40 respectively) and an arcing contact (31, 41 respectively), with one of the two contacts (3) being fixed to a blast or extinguishing nozzle (32). According to the invention, the second contact (4) and the drive bar (70) are joined together by coupling means (6) in such a way that they move together in translation in the same direction, the transmission means (5) being disposed on the side (21) of the chamber (2) that is adjacent to the drive bar (70), and are adapted to transmit the motion of the driven second contact (4) to the first contact (3).
Type:
Application
Filed:
April 14, 2008
Publication date:
October 23, 2008
Applicant:
Tour AREVA
Inventors:
Joel Ozil, Christophe Creusot, Jean-Luc Bourgeois, Christian Lindner
Abstract: The patent describes an electric switchgear (10) with a pole of the switchgear filled with insulating gas, and it is provided with a monitoring device (14) for the insulating gas in the switchgear pole and with a test connection (28) for a testing device to test the monitoring device (14). A device (20) is provided that has a test connection (28). The device (20) is connected to the monitoring device (14) and the switchgear pole. The device (20) has a valve (23), with which the switchgear pole can be detached from the monitoring device (14).
Abstract: A high or medium voltage electrical switch, particularly a GIS type isolating switch with three switching positions and a grounding position, includes a switching element in a closed and sealed enclosure that can be filled with a dielectrically insulating gas, containing a mobile switching element free to move along an axial direction to electrically connect two conducting bars at intervals from each other, and also including a fixed ground contact to be electrically connected to one of the two conducting bars through the switching element when the switch is in the grounding position. The fixed ground contact is offset from the path of the switching element along the axial direction and the switching element forms a Y with a contact pin such that the contact pin and the fixed ground contact engage in each other through displacement of the switching element along the axial direction.
Type:
Grant
Filed:
August 6, 2004
Date of Patent:
September 30, 2008
Assignee:
Areva T&D SA
Inventors:
Vladimir Gutalj, Andre Doessegger, Hugo Hiltbrunner
Abstract: This method comprises the steps of transmitting a beam of light onto a surface (17) of an element (1) comprising a fissile material, passing the beam of light reflected by the surface into a polarisation analyser (27) having a modifiable analysis direction, transmitting the beam from the polarisation analyser (27) to a device (31) for acquiring digital images, acquiring at least one digital image (31) of the surface (17) of the element (1) and processing the digital image acquired in order to measure the anisotropy. Use, for example, in controlling particles of nuclear fuel for an HTR/VHTR type reactor.
Type:
Application
Filed:
March 16, 2006
Publication date:
September 25, 2008
Applicants:
Areva NP, Commissariat A L'Energie Atomique
Inventors:
Gregory Maveyraud, Jean-Marie Vallerot, Xavier Bourrat, Olivier Dugne
Abstract: In a computer modeling method for the core of a nuclear reactor the core is divided into a plurality of primary grids in the form of coarse mesh cells. A sub-section of the core relating to at least one grid is assigned to that grid. The sub-section includes that grid and a buffer zone that surrounds the grid horizontally and contains at least the grid that lies immediately adjacent to the first grid. The sub-section is sub-divided into a plurality of secondary grids—fine mesh cells—that are smaller than the primary grids. In a first computing step, a model of the core is calculated using a nodal calculation method, based on a respective dataset that is assigned to each primary grid. In a second computing step, a respective second dataset is assigned to each secondary grid of a sub-section and a model is then calculated for the sub-section, based on the dataset and the flows on the border of the sub-section that have been calculated in the first computing step.
Abstract: The present invention relates to a vacuumable gel that can be used for decontaminating surfaces, and also to the use of this gel. The decontamination may be, for example, a radioactive decontamination. The gel of the present invention is composed of a colloidal solution. It comprises from 5 to 25 wt % of an inorganic viscosity modifier relative to the total weight of the gel; from 0.01 to 0.2 wt % of a surfactant relative to the total weight of the gel, and, particularly preferably, a surfactant in an amount strictly below 0.1 wt % relative to the total weight of the gel; from 0.5 to 7 mol, per litre of gel, of an inorganic acid or base; and optionally from 0.05 to 1 mol, per litre of gel, of an oxidizer having a standard redox potential E0 greater than 1.4 V in a strong acid medium or of the reduced form of this oxidizer; the remainder being water. It may be applied, by spraying, to a surface to be decontaminated, and removed in the form of dry residues by suction or brushing after drying.
Type:
Application
Filed:
October 3, 2006
Publication date:
September 18, 2008
Applicants:
COMMISSARIAT A L'ENERGIE ATOMIQUE, AREVA NC
Inventors:
Sylvain Faure, Paul Fuentes, Yvan Lallot
Abstract: A device for the actuation of the movable contacts of a hybrid circuit breaker allows the following time diagram to be implemented: command the opening of the interrupting chamber, offset the opening of the vacuum switch so as to allow the interrupting chamber contacts to separate at a minimum speed and in a way that is synchronous with the separation of the vacuum switch contacts, close the vacuum switch while keeping the interrupting chamber in the open position. Moreover, closing the interrupting chamber does not act upon the contacts of the vacuum switch.
Type:
Grant
Filed:
October 21, 2005
Date of Patent:
September 16, 2008
Assignee:
Areva T&D SA
Inventors:
Andre Neveu, Andre Cimala, Alain Girodet, Mehdi Lebiad, Gwenael Marquezin
Abstract: A fuel element for a nuclear reactor has a fuel rod bundle, at least one spacer with cells defined by at least one web section made from a first material and several guide tubes each running through a cell and axially fixed thereto made from a second material. The first and second materials have differing thermal expansion coefficients. The connection between the guide tube and the spacer is embodied as follows: first and second projections are directly or indirectly fixed to the guide tube. The first projections are disposed in a first axial position and the second projections are arranged at a second axial position and the projections each engage in an opening through the web section to give an axially-acting undercut.
Type:
Application
Filed:
October 30, 2007
Publication date:
September 11, 2008
Applicant:
AREVA NP GmbH
Inventors:
Matthias Rudolph, Hans-Peter Fuchs, Erhard Friedrich
Abstract: A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form to improve heat transfer and reduce corrosion is provided. The nanoparticles are delivered to a closed cooling circuit such as a CCWS. Methods for providing the nanoparticles are also provided.
Abstract: A nuclear power plant provides for delivery of nanoparticles to coolant found in the containment, for example during severe accident scenarios. The nanoparticles advantageously can be delivered passively or actively independently of any emergency core cooling system. The nanoparticle supply can include for example tanks storing nanofluids or solid nanoparticles, or dissolvable paints containing nanoparticles. Methods for providing the nanoparticles are also provided.
Type:
Application
Filed:
March 6, 2007
Publication date:
September 11, 2008
Applicant:
AREVA NP
Inventors:
Mihai G.M. Pop, Brian Glenn Lockamon, Angelo Beati
Abstract: A device and method to move a fuel assembly of a nuclear reactor, wherein the device eliminates the potential for dropping the fuel assembly due to stress corrosion cracking of the upper guide thimble sleeves that attach the top nozzle to guide thimbles.
Type:
Grant
Filed:
June 11, 2007
Date of Patent:
September 9, 2008
Assignee:
Areva NP Inc.
Inventors:
George S. Pabis, Darel R. Clark, Anthony A. Pugh, Raymond A. King
Abstract: A fuel element for a pressurized water reactor has fuel rods guided through a number of axially spaced spacers. The spacers form a square grid with mesh openings arranged in rows and columns. Support tubes that do not contain fuel pass through a number of the mesh holes and are joined to the meshes . The support tubes are spread out in positions within the grid with a predetermined number of support tubes and a distribution thereof within the grid, which is rotationally symmetric about 90° with regard to a rotation about the central axis of the spacer, the central axis is perpendicular to the grid plane, the number of rows and columns that do not contain any support tubes is minimal. Optionally, remaining inner rows and columns that do not contain any support tubes are not situated next to one another.
Type:
Grant
Filed:
December 28, 2004
Date of Patent:
September 9, 2008
Assignee:
Areva NP GmbH
Inventors:
Jürgen Stabel, Udo Borsdorf, Hans-Peter Hübsch
Abstract: A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form is provided. The nanoparticles are delivered in locations such as the cold leg accumulator and high and low pressure pumps of an emergency core cooling system. Motor driven valves and pressurization can aid in the delivery. Methods for providing the nanoparticles are also provided.
Abstract: The inventive photothermal test camera (16) is provided with a laser beam (4) shaping system (22) comprising a device (40) for extending the laser beam section in such a way that a heating area (2) extended in a direction (D) is formed on the surface of a testable piece (1), an array (8) of infrared sensors (10) for detecting a infrared radiation transmitted by a detection area (3) on the surface (1a) of the piece (1) with respect to the heating area (2) and a unit (46) for processing signals transmitted by the infrared sensors (10) in such a way that a thermographic image of the piece (1) surface (1a) is produced by scanning said surface (1a) with the aid of the heating area (2). An extending device (40) is embodied in the form of an optical device. Said invention can be used for non-destructive testing.
Abstract: A method to characterize the power transfer of a nuclear component is provided including the steps of obtaining a sample of a deposit layer on a side of a nuclear component, obtaining a scanning electron microscope image of an outside surface of the sample, obtaining a scanning electron microscope image of an inside surface of the sample, analyzing the scanning electron microscope images of the outside and inside surfaces of the sample for a presence of capillaries and steam chimneys, and calculating the power transfer of the component based on a number of steam chimneys in the deposit layer.
Type:
Grant
Filed:
June 9, 2006
Date of Patent:
September 2, 2008
Assignee:
Areva NP, Inc.
Inventors:
Mihai G. M. Pop, John Carroll Griffith, William Edward Allmon, Brian Glenn Lockamon
Abstract: A spacer for a fuel element of a boiling water reactor contains cells that are formed by inner partitions, which are disposed in a crisscross manner, and by outer partitions, which surround the inner partitions in a frame-like manner. A guiding device is placed on the spacer and contains a flow-through opening, which is located in an outer partition. The guiding device also contains a guiding element which, when viewed in the direction of flow of the coolant, is located in front of the flow-through opening, and is situated at a distance from the inner side of the outer partition, and interacts with the flow-through opening like a venturi nozzle.
Abstract: A spacer for a fuel assembly for a light water nuclear reactor contains a plurality of intercrossed segments, which form a grid. The segments are formed from first and second metal strips which are assembled and provided with protruding parts or corrugations in such a way that the adjacent protruding parts are embodied in such a way that a flow component perpendicular to a vertical central plane which extends between the metal strips is applied to cold water running out from the flow sub-channel.
Abstract: Supports for high or medium voltage electrical conductors (6, 7) at potentials different from the potential of an enclosure (1) are supported by disc-shaped parts (4, 5) made from thermoplastic polyester, for example terephthalate polyethylene. The discs (4 and 5) provide good insulation without largely disturbing the electrical field around the conductors due to their fairly low dielectric constant. They are also compatible with use under SF6 gas.
Type:
Application
Filed:
September 28, 2005
Publication date:
August 14, 2008
Applicant:
AREVA T & D AG
Inventors:
Hugo Hiltbrunner, Gerardo Palmieri, Karsten Pohlink, Christian Tschannen, Jean-Luc Bessede, Yannick Kieffel
Abstract: The invention relates to a method of decontaminating an oxide layer-comprising surface of a component or a system of a nuclear facility, wherein the oxide layer is treated with gaseous nitrogen oxide (NOx) as oxidizing agent.
Type:
Application
Filed:
April 15, 2008
Publication date:
August 14, 2008
Applicant:
AREVA NP GMBH
Inventors:
Horst-Otto Bertholdt, Terezinha Claudete Maciel, Franz Strohmer